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{{#Wiki_filter:U.S. NUCLEAR REGULATORY CoMMIS510N NRC FORM 366 (7 77)
{{#Wiki_filter:U.S. NUCLEAR REGULATORY CoMMIS510N NRC FORM 366 (7 77)
* LICENSEE EVENT REPORT
* LICENSEE EVENT REPORT CONTROL 8 LOCK: l 1
    .
CONTROL 8 LOCK: l 1
l    l    l    l  l 6
l    l    l    l  l 6
lh              (PL EASE PRINT OR TYPE ALL REQUIRED INFORMATION) lo l 8t 9l l 0l LICE?.SEE Hl DCODE    l Bl Sl 1l@l 0 l 0 l -lLICENSE              0 l 0NOVHEH l N l P I F l 25- l 026 ] 3LICENSE      ]@l 411PEl 1JO l l 57l 1l l
lh              (PL EASE PRINT OR TYPE ALL REQUIRED INFORMATION) lo l 8t 9l l 0l LICE?.SEE Hl DCODE    l Bl Sl 1l@l 0 l 0 l -lLICENSE              0 l 0NOVHEH l N l P I F l 25- l 026 ] 3LICENSE      ]@l 411PEl 1JO l l 57l 1l l
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0 l 21 DATE 2 181719  74      75
                                                                                                                                         @l0l3l1l2l7l9l@
                                                                                                                                         @l0l3l1l2l7l9l@
REPORT DATE        80 7          8                    60            61            DOCKET NUV8ER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l o 12 l l At 0532 hours on 2/28/79, Startup Transfomer 01 was taken out of service for adjust- 1 l
REPORT DATE        80 7          8                    60            61            DOCKET NUV8ER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l o 12 l l At 0532 hours on 2/28/79, Startup Transfomer 01 was taken out of service for adjust- 1 l
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o    4 o s        I personnel realized that surveillance tests should have been perforc;ed, and testing was]
o    4 o s        I personnel realized that surveillance tests should have been perforc;ed, and testing was]
l o 16 ] l completed by 0744 hours on 2/28/79. The alternate of f site AC electrical power source l l o l 7 l l was in service and subsequent surveillance tests showed both Emergency Diesel Genera- l l
l o 16 ] l completed by 0744 hours on 2/28/79. The alternate of f site AC electrical power source l l o l 7 l l was in service and subsequent surveillance tests showed both Emergency Diesel Genera- l l
o  a 1 tors to be operable.                                (NP-32-79-01)                                                                                          80 CAUSE                                                    COMP.          VALVE SYST E M          CAUSE SU8 CODE              COVPoNENT CODE                  SUBCODE          SUBCODE CODE              CODE 8                                  IE lA l @ lA l@                        A l @ l Z ] Z l Z l Z l Z l Z l@ [ Zj @ [Z_j                        20
o  a 1 tors to be operable.                                (NP-32-79-01)                                                                                          80 CAUSE                                                    COMP.          VALVE SYST E M          CAUSE SU8 CODE              COVPoNENT CODE                  SUBCODE          SUBCODE CODE              CODE 8                                  IE lA l @ lA l@                        A l @ l Z ] Z l Z l Z l Z l Z l@ [ Zj @ [Z_j                        20 12            13                          18            13 7        8                        9          10          Il REVISION SEQUENTI AL                    OCCURRENCE            REPORT CODE                TYPE                        NO.
                                                                                                                                                      @
12            13                          18            13 7        8                        9          10          Il REVISION SEQUENTI AL                    OCCURRENCE            REPORT
_
CODE                TYPE                        NO.
REPORT No.
REPORT No.
h gEP, LE R Ro      EVENT YEAR l7 l9                [---J      l0 l2 l3 l            l/l          l0l1l                  l Tl          l--l 31 y32 23          24            26      27            28      29            30
h gEP, LE R Ro      EVENT YEAR l7 l9                [---J      l0 l2 l3 l            l/l          l0l1l                  l Tl          l--l 31 y32 23          24            26      27            28      29            30
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       ,  3      l should have been perf ormed. Testing was completed by 0744 hours on 2/28/79.
       ,  3      l should have been perf ormed. Testing was completed by 0744 hours on 2/28/79.
1 4      l                                                                                                                                                      80 7        8 9
1 4      l                                                                                                                                                      80 7        8 9
                                     ".POWE7                      oTHERS1ATUS              ISCO RY                              DISCOVERY DESCRIPTICN ST      S li 15 I [_EJg l 0 [ 8 l 5 l@l NA                                                      l  l A [gl        NA
                                     ".POWE7                      oTHERS1ATUS              ISCO RY                              DISCOVERY DESCRIPTICN ST      S li 15 I [_EJg l 0 [ 8 l 5 l@l NA                                                      l  l A [gl        NA ACTIVITY CO TENT                                                                                              LOCATION oF RELEASE RELEASED OF RELEASE                        AMOUNT oF ACTIVITY NA                                                                      l
  '
: 6                                                                              l 7      8  9 l Zl @ l10Z lh NA          11                                      44        45 80 FERSONNEL E XPOSURES NUP/8 E R          TYPE        DESCRIPTION NA                                                                                                              l 1 7      l 0] 0l 0                l Zl@l                                                                                                                        *
* ACTIVITY CO TENT                                                                                              LOCATION oF RELEASE RELEASED OF RELEASE                        AMOUNT oF ACTIVITY NA                                                                      l
: 6                                                                              l 7      8  9 l Zl @ l10Z lh NA          11                                      44        45
                                                                                                                                                                      .
80 FERSONNEL E XPOSURES NUP/8 E R          TYPE        DESCRIPTION NA                                                                                                              l 1 7      l 0] 0l 0                l Zl@l                                                                                                                        *
   '        ' ' ,ERsONNELiN,uLS  ''                    ''
   '        ' ' ,ERsONNELiN,uLS  ''                    ''
                       ~u ,eE R            DESCR,Puo~@
                       ~u ,eE R            DESCR,Puo~@
l t R        l 01 01 0111 @ 12] NA                                                                                                                                  80 7        8 9 LOSS OF DESCnipTioN On DAVAGE To FAClllTY h TYPE                                      v
l t R        l 01 01 0111 @ 12] NA                                                                                                                                  80 7        8 9 LOSS OF DESCnipTioN On DAVAGE To FAClllTY h TYPE                                      v
       ' o                                                                                                                                                                  l
       ' o                                                                                                                                                                  l LZJ @ l NA                                                                                                                                              *
            "
LZJ @ l NA                                                                                                                                              *
  '            '
                                '
                 ,SSJ'@*"$5OR,P110N                                      7903160157-@
                 ,SSJ'@*"$5OR,P110N                                      7903160157-@
nnC USE ONLy lllllllllllll3 2 o        l N f l NA                                                                                                                l 68 69                          83*5 7        8 9            10
nnC USE ONLy lllllllllllll3 2 o        l N f l NA                                                                                                                l 68 69                          83*5 7        8 9            10 DVR 79-044
* DVR 79-044                                                           *
* PHONE:
                                                                                                                -
PHONE:
                                                                                                                                                            '
NAME OF PREPARER .
NAME OF PREPARER .


.
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-32-79-01 DATE.0F EVENT:    February 28, 1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE:    Failure to comply to Technical Specifications with Startup Transformer 01 out of service Conditions Prior to Occurrence: The unit was in Mode 1, with Power (MUT) = 2341, and Load (Gross MWE) = 792.
.
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-32-79-01
                      .
DATE.0F EVENT:    February 28, 1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE:    Failure to comply to Technical Specifications with Startup Transformer 01 out of service Conditions Prior to Occurrence: The unit was in Mode 1, with Power (MUT) = 2341, and Load (Gross MWE) = 792.
Description of Occurrence: At 0532 hours on February 28, 1979, 345 KV - 13.8 KV Startup Transf ormer "01" was taken out of service for transformer tap setting adjust-ments. This Lamediately entered the unit into Action Statement (a) of Technical Speci-fication 3.8.1.1. Action Statement (a) o f Technical Specification 3.8.1.1 requires operations personnel to verify correct breaker alignment and power availability by performing Surveillance Test ST 5080.01, " Independent Off-Site AC Sources Lined up and Available", and to verify that each Emergency Diesel Cencrator is operable by perform-ing Surveillance Test ST 5081.01, " Diesel Generator Monthly Test", within one hour and every eight hours thereafter until the transformer is placed back in service. Opera-tions personnel misinterpreted this Action Statement and failed to do the required surveillance testing.
Description of Occurrence: At 0532 hours on February 28, 1979, 345 KV - 13.8 KV Startup Transf ormer "01" was taken out of service for transformer tap setting adjust-ments. This Lamediately entered the unit into Action Statement (a) of Technical Speci-fication 3.8.1.1. Action Statement (a) o f Technical Specification 3.8.1.1 requires operations personnel to verify correct breaker alignment and power availability by performing Surveillance Test ST 5080.01, " Independent Off-Site AC Sources Lined up and Available", and to verify that each Emergency Diesel Cencrator is operable by perform-ing Surveillance Test ST 5081.01, " Diesel Generator Monthly Test", within one hour and every eight hours thereafter until the transformer is placed back in service. Opera-tions personnel misinterpreted this Action Statement and failed to do the required surveillance testing.
At 0730 hours on February 28, 1979, operations personnel realized that Surveillance Tests ST 5080.01 and ST 5081.01 should have been performed, and testing was completed by 0744 hours on February 28, 1979.
At 0730 hours on February 28, 1979, operations personnel realized that Surveillance Tests ST 5080.01 and ST 5081.01 should have been performed, and testing was completed by 0744 hours on February 28, 1979.
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Failure to complete Surveillanco Tests ST 5080.01 and ST 5081.01 within one hour of taking Startup Transformer "01" out of service placed the unit in violation of Limit-ing Condition for Operation 3.0.3 which requires that in the event that a limiting condition f or operation and/or associated action requirements cannot be satisfied because of circumstances in excess of those addressed in the specifications, the unit shall be in hot standby within one hour and in cold shutdown within 30 hours unless corrective measures are completed.
Failure to complete Surveillanco Tests ST 5080.01 and ST 5081.01 within one hour of taking Startup Transformer "01" out of service placed the unit in violation of Limit-ing Condition for Operation 3.0.3 which requires that in the event that a limiting condition f or operation and/or associated action requirements cannot be satisfied because of circumstances in excess of those addressed in the specifications, the unit shall be in hot standby within one hour and in cold shutdown within 30 hours unless corrective measures are completed.
LER #79-023
LER #79-023
                                                                                .
                                                      .


       ~
       ~
  .
'.
        -
  ..
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE                                PAGE 2 OF 2 SUPPLDIENTAL INFORMATION FOR LER NP-32-79-01 Designation of Apparent Cause of Occurrence: This incident was caused by personnel error. Operations personnel misinterpreted Action Statement (a) of Technical Speci-fication 3.8.1.1 and f ailed to perf orm the required surveillance.
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE                                PAGE 2 OF 2 SUPPLDIENTAL INFORMATION FOR LER NP-32-79-01 Designation of Apparent Cause of Occurrence: This incident was caused by personnel error. Operations personnel misinterpreted Action Statement (a) of Technical Speci-fication 3.8.1.1 and f ailed to perf orm the required surveillance.
Analysis of Occurrence: There was no danger to the health and safety of the public or to unit personnel. The alternate offsi.te AC electrical power source was in service supplying the auxiliary loads for the unit at the time of the incident and subsequent surveillance tests showed both Emergency Diesel Generators to be operable.
Analysis of Occurrence: There was no danger to the health and safety of the public or to unit personnel. The alternate offsi.te AC electrical power source was in service supplying the auxiliary loads for the unit at the time of the incident and subsequent surveillance tests showed both Emergency Diesel Generators to be operable.
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Failure Data:  There have been no previously reported similar incidents.
Failure Data:  There have been no previously reported similar incidents.
LER #79-023                                                        .
LER #79-023                                                        .
                                              .
                                                                                              *.
e 9
e 9
                                                                                             .}}
                                                                                             .}}

Latest revision as of 16:28, 1 February 2020

LER 79-023/01T-0 on 790228:Startup Transformer 01 Taken Out of Svc;Surveillance Tests Not Performed within One Hour, Contrary to Tech Spec Requirements.Caused by Personnel Error.Testing Completed as Soon as Error Realized
ML19282B717
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 03/12/1979
From: David Brown
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19282B711 List:
References
LER-79-023-01T, LER-79-23-1T, NUDOCS 7903160152
Download: ML19282B717 (3)


Text

U.S. NUCLEAR REGULATORY CoMMIS510N NRC FORM 366 (7 77)

  • LICENSEE EVENT REPORT CONTROL 8 LOCK: l 1

l l l l l 6

lh (PL EASE PRINT OR TYPE ALL REQUIRED INFORMATION) lo l 8t 9l l 0l LICE?.SEE Hl DCODE l Bl Sl 1l@l 0 l 0 l -lLICENSE 0 l 0NOVHEH l N l P I F l 25- l 026 ] 3LICENSE ]@l 411PEl 1JO l l 57l 1l l

CAT1l@l 58 l@

7 14 15 CON'T lolil 3o[n$ l L j@l 0l 5 l O! -l 0 l 3 l 463 l 669l@l EVENT 0 l 21 DATE 2 181719 74 75

@l0l3l1l2l7l9l@

REPORT DATE 80 7 8 60 61 DOCKET NUV8ER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l o 12 l l At 0532 hours0.00616 days <br />0.148 hours <br />8.796296e-4 weeks <br />2.02426e-4 months <br /> on 2/28/79, Startup Transfomer 01 was taken out of service for adjust- 1 l

I o I a l l ments. This immediately entered the unit into Action Statement (a) of Tech Spec l 3.8.1.1 which requires surveillance tests be performed within one hour. At 0730 hour0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />s]

o 4 o s I personnel realized that surveillance tests should have been perforc;ed, and testing was]

l o 16 ] l completed by 0744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br /> on 2/28/79. The alternate of f site AC electrical power source l l o l 7 l l was in service and subsequent surveillance tests showed both Emergency Diesel Genera- l l

o a 1 tors to be operable. (NP-32-79-01) 80 CAUSE COMP. VALVE SYST E M CAUSE SU8 CODE COVPoNENT CODE SUBCODE SUBCODE CODE CODE 8 IE lA l @ lA l@ A l @ l Z ] Z l Z l Z l Z l Z l@ [ Zj @ [Z_j 20 12 13 18 13 7 8 9 10 Il REVISION SEQUENTI AL OCCURRENCE REPORT CODE TYPE NO.

REPORT No.

h gEP, LE R Ro EVENT YEAR l7 l9 [---J l0 l2 l3 l l/l l0l1l l Tl l--l 31 y32 23 24 26 27 28 29 30

._21 22 HOURS 22 SUB IT D FOR1 8. SUPPLIE MAN FACT RER AK r ATO oN PL NT T l33XJ@l l@ lZi@ IZ @ 10!010I l 1Y [g 41 l

42

[g l43Z l@ lZ 44 lZ lZ lZ @

47

_ 34 35 36 31 40 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l

li l o j l This incident was caused by personnel error. Operations personnel misinterpreted lT[7] l Action Statement (a) of Tech Spec 3.8.1.1 and f ailed to perform the required surveil- I

, , l lance. At 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />, operations personnel realized that the surveillance tests l .,

l

, 3 l should have been perf ormed. Testing was completed by 0744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br /> on 2/28/79.

1 4 l 80 7 8 9

".POWE7 oTHERS1ATUS ISCO RY DISCOVERY DESCRIPTICN ST S li 15 I [_EJg l 0 [ 8 l 5 l@l NA l l A [gl NA ACTIVITY CO TENT LOCATION oF RELEASE RELEASED OF RELEASE AMOUNT oF ACTIVITY NA l

6 l 7 8 9 l Zl @ l10Z lh NA 11 44 45 80 FERSONNEL E XPOSURES NUP/8 E R TYPE DESCRIPTION NA l 1 7 l 0] 0l 0 l Zl@l *

' ' ' ,ERsONNELiN,uLS

~u ,eE R DESCR,Puo~@

l t R l 01 01 0111 @ 12] NA 80 7 8 9 LOSS OF DESCnipTioN On DAVAGE To FAClllTY h TYPE v

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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-32-79-01 DATE.0F EVENT: February 28, 1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Failure to comply to Technical Specifications with Startup Transformer 01 out of service Conditions Prior to Occurrence: The unit was in Mode 1, with Power (MUT) = 2341, and Load (Gross MWE) = 792.

Description of Occurrence: At 0532 hours0.00616 days <br />0.148 hours <br />8.796296e-4 weeks <br />2.02426e-4 months <br /> on February 28, 1979, 345 KV - 13.8 KV Startup Transf ormer "01" was taken out of service for transformer tap setting adjust-ments. This Lamediately entered the unit into Action Statement (a) of Technical Speci-fication 3.8.1.1. Action Statement (a) o f Technical Specification 3.8.1.1 requires operations personnel to verify correct breaker alignment and power availability by performing Surveillance Test ST 5080.01, " Independent Off-Site AC Sources Lined up and Available", and to verify that each Emergency Diesel Cencrator is operable by perform-ing Surveillance Test ST 5081.01, " Diesel Generator Monthly Test", within one hour and every eight hours thereafter until the transformer is placed back in service. Opera-tions personnel misinterpreted this Action Statement and failed to do the required surveillance testing.

At 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> on February 28, 1979, operations personnel realized that Surveillance Tests ST 5080.01 and ST 5081.01 should have been performed, and testing was completed by 0744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br /> on February 28, 1979.

With the exception of the initial surveillance requirement, all other surveillance re-

quirements were met until Startup Transformer "01" was returned to service at 1845 hours0.0214 days <br />0.513 hours <br />0.00305 weeks <br />7.020225e-4 months <br /> on February 28, 1979.

Taking Startup Transformer "01" out of service placed the unit in Action Statement (a) of Technical Specification 3.8.1.1 which states that two independent circuits between the offsite transmission network and the onsite distribution system each consisting of one operabic 345 KV transmission line, one operable 345 KV - 13.8 KV Startup Trans-former, one operable 13.8 KV Bus, and one operable Emergency Diesel Generator system be operable.

Failure to complete Surveillanco Tests ST 5080.01 and ST 5081.01 within one hour of taking Startup Transformer "01" out of service placed the unit in violation of Limit-ing Condition for Operation 3.0.3 which requires that in the event that a limiting condition f or operation and/or associated action requirements cannot be satisfied because of circumstances in excess of those addressed in the specifications, the unit shall be in hot standby within one hour and in cold shutdown within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> unless corrective measures are completed.

LER #79-023

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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE PAGE 2 OF 2 SUPPLDIENTAL INFORMATION FOR LER NP-32-79-01 Designation of Apparent Cause of Occurrence: This incident was caused by personnel error. Operations personnel misinterpreted Action Statement (a) of Technical Speci-fication 3.8.1.1 and f ailed to perf orm the required surveillance.

Analysis of Occurrence: There was no danger to the health and safety of the public or to unit personnel. The alternate offsi.te AC electrical power source was in service supplying the auxiliary loads for the unit at the time of the incident and subsequent surveillance tests showed both Emergency Diesel Generators to be operable.

Corrective Action: At 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> on February 28, 1979, operations personnel realized that ST 5080.01 and ST 5081.01 should have been performed. Testing was completed by 0744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br /> on February 28, 1979.

Further corrective action will follow pending further investigation into the incident.

Failure Data: There have been no previously reported similar incidents.

LER #79-023 .

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